Method for extracting technetium from nuclear fuel post-treatment waste liquid

A technology for nuclear fuel and waste liquid, applied in the direction of improving process efficiency, can solve problems such as unfavorable purification of technetium products, and achieve the effect of small amount of radioactive waste and simple operation

Active Publication Date: 2019-08-20
CHINA INSTITUTE OF ATOMIC ENERGY +1
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

These kinds of reagents can extract technetium under acidic conditions, but they are also very strong in extracting actin

Method used

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  • Method for extracting technetium from nuclear fuel post-treatment waste liquid
  • Method for extracting technetium from nuclear fuel post-treatment waste liquid
  • Method for extracting technetium from nuclear fuel post-treatment waste liquid

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Effect test

Embodiment 1

[0031] Using the method for extracting technetium of the present invention to extract technetium from a certain nuclear fuel reprocessing waste liquid, the main steps are as follows:

[0032] (1) acid adjustment: the concentration of nitric acid containing pertechnetate radical nitric acid waste liquid is adjusted to 0.5mol / L;

[0033] (2) technetium extraction: use protonated tris(N'N-di-n-octylacetamido)amine as extractant (the alkyl group is a straight-chain alkyl group with 8 carbon atoms), and use kerosene as diluent The waste liquid is extracted and separated to obtain an organic phase; the concentration of the tris(N'N-di-n-octylacetamido)amine in the organic phase is 0.1mol / L;

[0034] (3) Tetravalent actinide element impurity washing: adopt the nitric acid solution containing oxalic acid to wash the organic phase that step (2) obtains, and the concentration of described oxalic acid is 0.2mol / L;

[0035] (4) Technetium back-extraction: Back-extract the technetium in t...

Embodiment 2

[0038] Using the method for extracting technetium of the present invention to extract technetium from a certain nuclear fuel reprocessing waste liquid, the main steps are as follows:

[0039] (1) acid adjustment: the concentration of nitric acid containing pertechnetate radical nitric acid waste liquid is adjusted to 1mol / L;

[0040] (2) technetium extraction: use protonated tris(N'N-di-n-decylacetamido)amine as extractant (the alkyl group is a straight-chain alkyl group with 12 carbon atoms), and use kerosene as diluent The waste liquid is extracted and separated to obtain an organic phase; the concentration of the tris(N'N-di-n-decylacetamido)amine in the organic phase is 0.2mol / L;

[0041] (3) Washing of tetravalent actinide impurities: the organic phase obtained in step (2) is washed with nitric acid solution containing oxalic acid, and the concentration of said oxalic acid is 0.1mol / L;

[0042] (4) Technetium back-extraction: Back-extract the technetium in the organic ph...

Embodiment 3

[0045] Using the method for extracting technetium of the present invention to extract technetium from a certain nuclear fuel reprocessing waste liquid, the main steps are as follows:

[0046](1) acid adjustment: the concentration of nitric acid containing pertechnetate radical nitric acid waste liquid is adjusted to 0.75mol / L;

[0047] (2) technetium extraction: use protonated tris(N'N-di-n-butylacetamido)amine as extractant (the alkyl group is a straight-chain alkyl group with 4 carbon atoms), and use kerosene as diluent The waste liquid is extracted and separated to obtain an organic phase; the concentration of the tris(N'N-di-n-butylacetamido)amine in the organic phase is 0.05mol / L;

[0048] (3) Tetravalent actinide element impurity washing: adopt the nitric acid solution containing EDTA to wash the organic phase that step (2) obtains, and the concentration of described EDTA is 0.3mol / L;

[0049] (4) Technetium back-extraction: back-extract the technetium in the organic ph...

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Abstract

The invention provides a method for extracting technetium from a nuclear fuel post-treatment waste liquid. The method comprises the following steps of (1), adjusting nitric acid concentration of nitric acid waste liquid containing high technetium acid radical to 2 mol/L; (2), extracting the high-technetium acid radical ions in the waste liquid, and separating to obtain an organic phase; (3), washing the organic phase obtained in the step (2) by adopting an oxalic acid-containing nitric acid solution; and (4), reversely extracting technetium in the organic phase by using an alkaline aqueous solution to obtain a technetium product solution. According to the method, extraction and purification of technetium in the nuclear fuel post-treatment nitric acid waste liquid are effectively realized;the method for extracting technetium is simple to operate, and can be applied to a traditional PUREX flow post-treatment plant, the concentration and the concentration of nitric acid of technetium inthe treated object can be higher, the composition of the waste liquid can be relatively complicated, and the generation amount of a radioactive waste in the treatment process is smaller.

Description

technical field [0001] The invention belongs to the field of nuclear fuel reprocessing, in particular to a method for extracting technetium from nuclear fuel reprocessing waste liquid. Background technique [0002] Technetium-99 is a long-lived fission product with a high yield in nuclear reactors, the fission yield is about 6%, and the half-life is about 2.11×10 5 year. Technetium-99 has strong mobility. In the geological disposal of radioactive waste, technetium-99 can migrate from vitrified body to groundwater, which has potential long-term radiation hazard risks to the biosphere. The safest way to dispose of technetium-99 is to extract it from nuclear fuel reprocessing radioactive waste liquid, and transform it into a stable or short-lived ruthenium isotope through thermal neutron transmutation, completely eliminating its hazards. [0003] At present, there are mainly the following ways to extract technetium from nuclear fuel reprocessing waste liquid: [0004] (1) Th...

Claims

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Application Information

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IPC IPC(8): C22B61/00C22B7/00
CPCC22B7/006C22B61/00Y02P10/20
Inventor 王辉丁颂东晏太红郑卫芳左臣王学羽王志鹏申震刘方
Owner CHINA INSTITUTE OF ATOMIC ENERGY
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